IR 05000458/2019011
| ML19095B499 | |
| Person / Time | |
|---|---|
| Site: | River Bend  |
| Issue date: | 04/05/2019 |
| From: | Ray Kellar Division of Reactor Safety IV |
| To: | Vercelli S Entergy Operations |
| Kellar R | |
| References | |
| IR 2019011 | |
| Download: ML19095B499 (17) | |
Text
April 5, 2019
SUBJECT:
RIVER BEND STATION, UNIT 1 - NRC PROBLEM IDENTIFICATION AND RESOLUTION INSPECTION REPORT 05000458/2019011
Dear Mr. Vercelli:
On February 28, 2019, the U.S. Nuclear Regulatory Commission (NRC) completed a problem identification and resolution inspection at River Bend Station and discussed the results of this inspection with Jeff Reynolds, Director, Regulatory & Performance Improvement and other members of your staff. The results of this inspection are documented in the enclosed report.
The NRC inspection team reviewed the stations corrective action program and the stations implementation to evaluate its effectiveness in identifying, prioritizing, evaluating, and correcting problems, and to confirm that the station was complying with NRC regulations and licensee standards for corrective action programs. Based on the samples reviewed, the team determined that your staffs performance in each of these areas adequately supported nuclear safety.
The team also evaluated the stations processes for use of industry and NRC operating experience information and the effectiveness of the stations audits and self-assessments.
Based on the samples reviewed, the team determined that your staffs performance in these areas adequately supported nuclear safety.
Finally, the team reviewed the stations programs to establish and maintain a safety-conscious work environment and interviewed station personnel to evaluate the effectiveness of these programs. Based on the teams observations and the results of these interviews the team found no evidence of challenges to your organizations safety-conscious work environment. Your employees appeared willing to raise nuclear safety concerns through at least one of the several means available.
The NRC inspectors did not identify any finding or violation of more than minor significance. This letter, its enclosure, and your response (if any) will be made available for public inspection and copying at http://www.nrc.gov/reading-rm/adams.html and at the NRC Public Document Room in accordance with 10 CFR 2.390, Public Inspections, Exemptions, Requests for Withholding.
Sincerely,
/RA Ray Azua Acting For/
Ray L. Kellar, P.E., Acting Team Leader Inspection Program and Assessment Team Division of Reactor Safety
Docket No. 50-458 License No. NPF-47
Enclosure:
Inspection Report 05000458/2019011 w/ Attachment: Information Request dated November 29, 2018
Inspection Report
Docket Number:
05000458
License Number:
Report Number:
Enterprise Identifier: I-2019-011-0000
Licensee:
Entergy Operations, Inc.
Facility:
River Bend Station
Location:
Saint Francisville, Louisiana
Inspection Dates:
February 11 - 28, 2019
Inspectors:
H. Freeman, Senior Reactor Inspector
P. Jayroe, Reactor Inspector
C. Jewett, Physical Security Inspector
B. Parks, Resident Inspector
Approved By:
Ray L. Kellar, P.E., Acting Team Leader
Inspection Program and Assessment Team
Division of Reactor Safety
SUMMARY
The U.S. Nuclear Regulatory Commission (NRC) continued monitoring the licensees performance by conducting a biennial problem identification and resolution inspection at River Bend Station, Unit 1 in accordance with the Reactor Oversight Process. The Reactor Oversight Process is the NRCs program for overseeing the safe operation of commercial nuclear power reactors. Refer to https://www.nrc.gov/reactors/operating/oversight.html for more information.
Findings and violations being considered in the NRCs assessment are summarized in the table below.
List of Findings and Violations
No findings were identified.
Additional Tracking Items
None.
INSPECTION SCOPES
Inspections were conducted using the appropriate portions of the inspection procedures (IPs)in effect at the beginning of the inspection unless otherwise noted. Currently approved IPs with their attached revision histories are located on the public website at http://www.nrc.gov/reading-rm/doc-collections/insp-manual/inspection-procedure/index.html.
Samples were declared complete when the IP requirements most appropriate to the inspection activity were met consistent with Inspection Manual Chapter (IMC) 2515, Light-Water Reactor Inspection Program - Operations Phase. The inspectors reviewed selected procedures and records, observed activities, and interviewed personnel to assess licensee performance and compliance with Commission rules and regulations, license conditions, site procedures, and standards.
OTHER ACTIVITIES - BASELINE
71152B - Problem Identification and Resolution 02.04 Biennial Team Inspection
The inspectors performed a biennial assessment of the licensees corrective action program, use of operating experience, self-assessments and audits, and safety-conscious work environment.
Corrective Action Program Effectiveness: The inspectors assessed the corrective action programs effectiveness in identifying, prioritizing, evaluating, and correcting problems and to confirm that the station was complying with NRC regulations and licensee procedures.
The team selected a sample of approximately 270 condition reports for review out of those that had been generated over the course of the assessment period beginning at the end of the previous biennial assessment on April 27, 2017. The selection included corrective action documents associated with 18 findings documented as non-cited violations in NRC inspection reports during the assessment period, 29 conditions that had been addressed by the licensee as Adverse Condition Analysis (cause analysis), and all 4 conditions that had been addressed as Root Cause Evaluations. Included in the sample was an in-depth review of condition reports associated with the emergency diesel generating system and the reactor protection system over a 5-year period. A listing of these documents can be found in the documents reviewed section of this report.
During the 2 weeks that the team was onsite, the team observed the licensees prioritization process by attending several screening committee meetings where department performance improvement coordinators provided recommendations on addressing issues documented in the corrective action process, and performance improvement review group meetings where managers reviewed and approved each issue (adverse or non-adverse, prioritization, and corrective actions) documented in the corrective action process.
To assess the adequacy of the licensees corrective action process, the team compared the licensees performance against regulatory requirements and licensing basis documents including: Title 10 of the Code of Federal Regulations Part 50, Appendix B, Criterion XVI, Corrective Action; Licensee Technical Specification 5.4.1 Procedures, as contained in Renewed Facility Operating License No. NPF-47; and against the licensees implementing procedures: EN-LI-102, "Corrective Action Program;" EN-LI-108, "Event Notification and Reporting;" EN-LI-118, "Cause Evaluation Process;" EN-LI-121, "Trending and Performance Review Process;" and EN-OP-104, "Operability Determination Process."
Operating Experience, Self-Assessments and Audits - The inspectors assessed the effectiveness of the stations processes for use of operating experience, audits and self-assessments. The team reviewed 46 Operating Experience written responses and condition reports that were developed based on information from a variety of sources including Title 10 of the Code of Federal Regulations, Part 21 notifications and other vendor correspondence, NRC generic communications, and publications from various industry groups including Institute of Nuclear Power Operations. The team reviewed 24 self-assessments and 12 audits that had been completed during the assessment period and interviewed the program engineer.
Safety-Conscious Work Environment - The inspectors assessed the effectiveness of the stations programs to establish and maintain a safety-conscious work environment. The team conducted safety-conscious work environment focus group interviews with 46 individuals from 5 different disciplines (maintenance, operations, engineering, planning/scheduling, nuclear independent oversight). Additionally, the team conducted individual interviews with 12 maintenance supervisors representing each of the maintenance organizations (electrical, mechanical, instrumentation and controls, fix-it-now). The team observed interactions between employees during the condition report screening meetings and during the Performance Improvement Review Group meetings.
The team interviewed the employee concerns coordinator and reviewed the results of the sites latest safety culture surveys and investigations related to safety-conscious work environment.
INSPECTION RESULTS
Observation - Corrective Action Program Assessment 71152B Based on the samples reviewed, the team determined that the licensees corrective action program (CAP) complied with regulatory requirements and self-imposed standards. The licensees performance in each of the areas of Problem Identification, Prioritization and Evaluation, and Corrective Actions adequately supported nuclear safety.
The team found that the licensee was identifying and documenting problems at an appropriately low threshold that supported nuclear safety. On average, the licensee was identifying and documenting over 6,600 condition reports (adverse and non-adverse) per year or approximately 170 per month. The number of condition reports initiated remained relative consistent with those from prior years.
The team found that the licensee was adequately prioritizing and evaluating problems. While the team did identify that (early in the assessment period) the licensee had been routinely characterizing some conditions associated with safety-related equipment as non-adverse [to quality] when it should have been adverse, these mischaracterizations did not adversely impact the prioritization or implementation of corrective actions to address the conditions.
The team noted that in 2018 the licensee had also identified they had been routinely using operability determinations to decide whether a documented condition was adverse or not and subsequently worked with the corporate office to add clarification to the corrective action procedure (EN-LI-102) on how a condition should be classified. The team found that the licensee's actions to address potential mischaracterizations appeared to be effective.
Over the assessment period, the team found that the licensee had generally developed and implemented corrective actions that were effective, timely, and - in cases of significant conditions adverse to quality - appeared to prevent recurrence. The team noted that while the licensee continued to experience degradation to nuclear fuel rods, the corrective actions that were scheduled to be installed during the next refueling outage were extensive and designed to reduce the chances of damage during future operations.
Observation - Self-Assessments and Audits Assessment 71152B Based on the samples reviewed and discussions with staff within the quality assurance and quality control organizations, the team determined that the licensee effectively performed self-assessments and audits. The samples reviewed were critical and challenged the status quo of the organization or program being assessed. Identified conditions were appropriately addressed within the corrective action program or through another licensee process. The team found that quality control and quality assurance staff reported to a manager within the corporate organization, and therefore, were independent of the onsite organization.
Observation - Operating Experience Assessment 71152B Based on the samples reviewed, the team determined the licensee appropriately evaluated industry operating experience for its relevance to the facility. Operating experience information was incorporated into plant procedures and processes as appropriate. The team further determined the licensee appropriately evaluated industry-operating experience when performing root cause analysis and apparent cause evaluations. The licensee appropriately incorporated both internal and external operating experience into lessons learned for training and pre-job briefs.
Observation - Safety-Conscious Work Environment Assessment 71152B Based on inspection interviews and insights obtained from safety culture and other relevant assessments, the team found that the licensee had established and maintained a safety-conscious work environment where individuals felt free to raise concerns without fear of retaliation. Employees indicated that they had numerous avenues for raising concerns which included talking to their supervisor, writing condition reports, using the chain-of-command (open door policy), the employee concerns program, the ethics hotline, or the NRC. Many individuals stated that they could take an issue all the way to the Site Vice President if they thought that they needed to do so to have their concern addressed properly.
The team noted that many of the individuals interviewed were relatively new to the site and industry - many had less than 3 years experience. The team learned that a significant percentage of the staff had changed during the previous few years, but that management was committed to hiring and training replacements. The team found that most of the organizations were fully staffed (if not fully qualified). While the staff turnover may continue to present challenges to the licensee regarding knowledge management/knowledge transfer, the team found that it did not adversely impact the safety-conscious work environment.
Finally, the team noted that the licensee had substantiated there were challenges to the safety-conscious work environment within the maintenance organization in mid-2018 and had made changes within the organization to address these challenges. Based upon the interviews, the team found that these changes appeared to be effective and did not identify the existence of issues that represented current challenges to the free flow of information or any underlying factors that could produce a reluctance to raise nuclear safety concerns.
EXIT MEETINGS AND DEBRIEFS
On February 28, 2019, the inspectors presented the biennial problem identification and resolution inspection results to Mr. J. Reynolds, Director, Regulatory & Performance Improvement and other members of the licensee staff. The inspectors verified no proprietary information was retained or documented in this report.
DOCUMENTS REVIEWED
71152Problem Identification and Resolution Biennial
Condition Reports (CR-RBS-YYYY-NNNNN unless otherwise noted)
2008-03020
2014-00794
2014-00816
2014-02698
2014-02961
2014-04164
2014-05471
2014-05472
2014-05821
2014-06122
2014-06616
2015-00237
2015-00451
2015-02686
2015-03277
2015-03291
2015-04816
2015-04817
2015-05296
2015-06129
2015-07606
2015-08293
2015-08503
2015-08559
2015-09136
2016-00416
2016-00584
2016-00770
2016-00890
2016-00893
2016-01370
2016-01430
2016-01451
2016-02202
2016-02715
2016-02962
2016-03324
2016-03519
2016-03784
2016-03882
2016-04125
2016-04838
2016-05616
2016-05620
2016-05810
2016-06213
2016-06859
2016-07717
2016-07737
2017-00168
2017-00669
2017-00678
2017-00691
2017-01409
2017-00156
2017-01684
2017-01716
2017-01740
2017-01918
2017-02046
2017-02058
2017-02228
2017-02238
2017-02242
2017-02284
2017-02640
2017-02773
2017-02790
2017-02828
2017-03082
2017-03349
2017-03377
2017-03424
2017-03445
2017-03533
2017-03704
2017-04046
2017-04128
2017-04375
2017-04431
2017-04560
2017-04566
2017-04663
2017-04843
2017-04907
2017-04961
2017-04961
2017-05078
2017-05261
2017-05419
2017-05568
2017-05575
2017-05630
2017-05875
2017-05989
2017-06008
2017-06031
2017-06064
2017-06090
2017-06118
2017-06206
2017-06316
2017-06518
2017-06618
2017-06656
2017-06998
2017-07047
2017-07076
2017-07079
2017-07348
2017-07378
2017-07543
2017-07623
2017-07777
2017-08060
2017-08198
2017-08270
2017-08275
2017-08294
2017-08299
2017-08310
2017-08362
2017-08490
2017-08563
2018-00027
2018-00028
2018-00057
2018-00224
2018-00294
2018-00320
2018-00352
2018-00523
2018-00613
2018-00776
2018-00780
2018-00780
2018-00780
2018-00922
2018-01085
2018-01365
2018-01417
2018-01735
2018-01743
2018-01916
2018-01967
2018-01980
2018-02105
2018-02314
2018-02400
2018-02417
2018-02454
2018-02597
2018-02687
2018-02738
2018-02765
2018-02768
2018-02771
2018-02775
2018-02780
2018-02880
2018-02960
2018-02978
2018-03095
2018-03145
2018-03146
2018-03149
2018-03424
2018-03537
2018-03572
2018-03630
2018-03666
2018-03715
2018-03751
2018-03804
2018-03882
2018-03910
2018-03952
2018-03971
2018-04078
2018-04297
2018-04382
2018-04612
2018-04613
2018-04783
Condition Reports (CR-RBS-YYYY-NNNNN unless otherwise noted)
2018-05054
2018-05057
2018-05225
2018-05334
2018-05563
2018-05635
2018-05725
2018-05752
2018-05776
2018-05876
2018-05915
2018-05978
2018-05992
2018-06038
2018-06084
2018-06300
2018-06352
2018-06363
2018-06497
2018-06677
2019-00097
2019-00106
2019-00316
2019-00341
2019-01025
2019-01058
2019-01108
2019-01156
2019-01160
HQN-2018-01495
HQN-2019-00316
Non-Cited Violations and Findings (NRC item number)
2017002-01
2017002-02
2017003-01
2017003-02
2017004-01
2017007-01
2017007-02
2017009-01
2018001-01
2018001-02
2018002-01
2018012-01
2018012-02
2018012-03
2018012-04
2018301-01
2018406-01
2018406-02
Work Orders
28397
411132
29154
436356-01
468033
468034
469554
473593
476316
476317
478993
479296
493161
499908
2684
2726753
QA Audits
Number Title Date
QA-10-2018-RBS-1
Quality Assurance Audit Report -
Maintenance
QA-12/18-2017-RBS-01
Quality Assurance Audit Report -
Operations / Tech Specs
QA-4-2018-RBS-01
Quality Assurance Audit Report -
Engineering (Design Control)
QA-3-2017-RBS-01
Quality Assurance Audit Report - Corrective
Action Program
QA-1-2017-RBS-1
Fitness-for-Duty and Access Authorization
Audit
08/14/2017
QA-1-2018-RBS-1
Fitness-for-Duty and Access Authorization
Audit
08/13/2018
QA-2-6-2017-RBS-1
Combined Chemistry, Effluents and
Environmental Monitoring Audit
09/18/2017
QA-7-2017-BRS-1
Emergency Plan Audit
05/08/2017
QA-7-2018-BRS-1
Emergency Plan Audit
05/07/2018
QA-14-15-2017-RBS-1
Combined Radiation Protection and
Radiation Waste Audit
10/23/2017
QA-16-2017-RBS-1
Security and Cyber Security Audit
2/06/2017
QA-16-2018-RBS-1
Security and Cyber Security Audit
2/03/2018
Self-Assessments
Number Title
LO-RLO-2016-00147
Chemistry and I&C Continuing Training programs
LO-RLO-2017-00016
Pre-NRC-Radiation Monitoring Instrumentation
LO-RLO-2017-00024
Pre-NRC Focused Self-Assessment: Radioactive Solid Waste
Processing and Radioactive Material Handling, Storage, and
Transportation
LO-RLO-2017-00025
Radioactive Gaseous and Liquid Effluent Treatment and
Radiological Environmental Monitoring Program
LO-RLO-2017-00030
Perform Snapshot Assessment - Verification of Emergency Facilities
On-Site and Off-Site Activity Topic: Controlled Document Annual
Audit
LO-RLO-2017-00033
Pre-NRC Inspection - Access Authorization
LO-RLO-2017-00034
Protection of Safeguards Information
LO-RLO-2017-00040 Snubber Program Compliance Focused Self-Assessment
LO-RLO-2017-00044 Self-Assessment - Confined Space
LO-RLO-2017-00055
(Pre-NRC FSA) Occupational Dose Assessment
LO-RLO-2017-00061
IP 71130.07 Security Training
LO-RLO-2017-00062
IP 71130.02 Access Control
LO-RLO-2017-00070
Pre-NRC Evaluated Exercise Assessment
LO-RLO-2017-00071
RP Pre-NRC Focused Self-Assessment Radiation Safety Inspection
IP 71124.01 - Radiological Hazard Assessment and Exposure
Controls
IP 71124.03 - In-Plant Airborne Radioactivity Control and Mitigation
IP 71151-OR01 - Occupational Exposure Control Effectiveness
LO-RLO-2017-00079
Industry OE: 2017 Utility TIF ACC 2-1: Student Evaluation Methods
LO-RLO-2017-00101 Annual Protection of Safeguards Information Self-Assessment
LO-RLO-2018-00023
3Month Followup Assessment on Fleet Sharing Events
LO-RLO-2018-00029
Department Compliance with Chemical Control and Waste
Management Requirements
LO-RLO-2018-00030 EN-MA-131 Lockout Tagout of Non-Plant Related Equipment
LO-RLO-2018-00032
Perform Snapshot Assessment - Verification of Emergency Facilities
On-Site and Off-Site: Controlled Document Annual Audit
LO-RLO-2018-00034
Perform Operating Experience (OE) Selfassessment
LO-RLO-2018-00047 Operator Fundamentals Informal Self-Assessment
LO-RLO-2018-00056 Operating Experience Self-Assessment
LO-RLO-2018-00083 EFIN Product Quality / Technical Rigor
Procedures
Number Title Revision
Hydraulic Stability Controls
Modifications
Procedures
Number Title Revision
MOV Thrust/Torque Setpoint Calculations
003
MOV Periodic Verification
005
MOV Test Data Review
006
Corrective Action Program
Corrective Action Program
Assessments and Benchmarking
Evaluation Process
Trending and Performance Review Process
Material Exclusion
Operating Experience Program
Determination Process
Emergency Operating Procedures and Severe Accident
Procedures Enclosures
2
GPM-0111
Tri-Nuclear Filter Operation
Other Docs:
EC 69975 2/26/17 Child EC for Logic Changes for HVC-ACU1A and HVC-ACU2A
EC 74740 Rev 0 Comparison of RBS Procedures 10 EGM 15-002 and DSS-ISG-2016-01 for
Enforcement Discretion for Tornado Generated Missile Non-Compliances
EC 62698 Rev 0 Disable the Self Diagnostic Trip on E31-N604D to a Light Indication Only
Calculation PM-194 Rev 11 Standby Cooling Tower Performance and Evaporation Losses
Without Drywell Unit Coolers
EN-MA-131 Lockout Tagout of Non-Plant Related Equipment
Information Request
Biennial Problem Identification and Resolution Inspection at River Bend Station
November 29, 2018
Inspection Report:
2019011
On-site Inspection Dates:
Weeks of February 11 and February 25, 2019
Assessment Period:
April 28, 2017, through March 1, 2019
This inspection will cover the period from April 28, 2017, through the end of the onsite
inspection. The scope of this request is information associated with activities during this
inspection period unless otherwise specified. To the extent possible, the requested information
should be provided electronically in word-searchable Adobe PDF (preferred) or Microsoft Office
format. Any sensitive information should be provided in hard copy during the teams first week
on site; we request that you do not provide sensitive or proprietary information electronically.
Lists of documents (summary lists) should be provided in Microsoft Excel or a similar sortable
format. Please ensure that the description field is not size limited such that the condition is
unclear. Please be prepared to provide any significant updates to this information during the
teams first week of on-site inspection. As used in this request, corrective action documents
refers to condition reports, notifications, action requests, cause evaluations, and/or other similar
documents.
Please provide the following information no later than January 18, 2019:
1.
Summary Document Lists
Note: For these summary lists, please include the document/reference number, the
document title, initiation date, current status, and long-text description of the issue.
a.
All corrective action documents related to significant conditions adverse to
quality that were opened, closed, or evaluated during the period
b.
All corrective action documents related to conditions adverse to quality that
were opened, closed or evaluated during the period
c.
All open corrective action documents related to conditions adverse to quality
that were first identified prior to the inspection period (April 28, 2017)
d.
All corrective action documents that were upgraded or downgraded in
priority/significance during the period (these may be limited to those
downgraded from, or upgraded to, apparent-cause level or higher)
e.
Corrective action documents initiated during the period that roll up multiple
similar or related issues, or that identify a trend
f.
Operator workarounds, operator burdens, temporary modifications, and control
room deficiencies (1) currently open and (2) that were evaluated and/or closed
during the period
g.
All prompt operability determinations (or other engineering evaluations) to
provide reasonable assurance of operability
h.
Plant safety issues raised or addressed by the Employee Concerns Program (or
equivalent) (sensitive information should be made available during the teams
first week on sitedo not provide electronically)
2.
Full Documents with Attachments
Note: Please include a summary list or index if document titles are not descriptive.
a.
Root Cause Evaluations completed during the period; include a list of any
planned or in progress
b.
Apparent Cause Evaluations completed during the period (if less than 20)
c.
Quality Assurance audits performed during the period
d.
Audits/surveillances performed during the period on the Corrective Action
Program, of individual corrective actions, or of cause evaluations
e.
Functional area self-assessments and non-NRC third-party assessments (e.g.,
peer assessments performed as part of routine or focused station self-and
independent assessment activities; do not include INPO assessments) that
were performed or completed during the period; include a list of those that are
currently in progress
f.
Any assessments of the safety-conscious work environment; if none performed
during the inspection period, provide the most recent
g.
Corrective action documents generated during the period associated with the
following:
i.
NRC findings and/or violations
ii.
Licensee Event Reports issued
h.
Corrective action documents generated for the following, if they were
determined to be applicable (for those that were evaluated but determined not
to be applicable, provide a summary list):
i.
NRC Information Notices, Bulletins, and Generic Letters issued or
evaluated during the period
ii.
Part 21 reports issued or evaluated during the period
iii.
Vendor safety information letters (or equivalent) issued or evaluated
during the period
iv.
Other external events and/or Operating Experience evaluated for
applicability during the period
i.
Corrective action documents generated for the following:
i.
Emergency planning drills and tabletop exercises performed during the
period
ii.
Maintenance preventable functional failures that occurred or were
evaluated during the period
iii.
Action items generated or addressed by offsite review committees
during the period
iv.
Comments, observations, or minor performance deficiencies identified or
documented during the 2017 NRC PI&R inspection or generated due to
inspector comments
3.
Logs and Reports
a.
Corrective action performance trending/tracking information generated during
the period and broken down by functional organization (if this information is fully
included in item 3.b, it need not be provided separately)
b.
Current system health reports, Management Review Meeting package, or
similar information; provide past reports as necessary to include 12 months of
metric/trending data
c.
Radiation protection event logs during the period
d.
Security event logs and security incidents during the period (sensitive
information should be made available during the teams first week on sitedo
not provide electronically)
e.
List of training deficiencies, requests for training improvements, and simulator
deficiencies for the period
Note: For items 3.c and 3.d, if there is no log or report maintained separate from the
corrective action program, please provide a summary list of corrective action program
items for the category described.
4.
Procedures
Note: For these procedures, please include all revisions that were in effect at any time
during the period.
a.
Corrective action program procedures, to include initiation and evaluation
procedures, operability determination procedures, cause evaluation procedures,
and any other procedures that implement the corrective action program
b.
Quality Assurance program procedures (specific audit procedures are not
necessary)
c.
Employee Concerns Program (or equivalent) procedures
d.
Procedures that implement/maintain a Safety Conscious Work Environment
e.
Conduct of Operations procedure (or equivalent) and any other procedures or
policies governing control room conduct, operability determination, operator
burdens and workarounds, etc.
f.
Operating Experience (OE) program procedures and any other procedures or
guidance documents that describe the sites use of OE information
5.
Other
a.
List of risk-significant components and systems, ranked by risk worth
b.
List of structures, systems, and components and/or functions that were in
maintenance rule (a)(1) status at any time during the inspection period; include
dates and results of expert panel reviews and dates of status changes
c.
Organization charts for plant staff and long-term/permanent contractors
d.
Electronic copies of the UFSAR (or equivalent), technical specifications, and
technical specification bases, if available
e.
Table showing the number of corrective action documents (or equivalent)
initiated during each month of the inspection period, by screened significance
f.
For each day the team is on site,
i.
Planned work/maintenance schedule for the station
ii.
Schedule of management or corrective action review meetings (e.g.
operations focus meetings, condition report screening meetings, CARBs,
MRMs, challenge meetings for cause evaluations, etc.)
iii.
Agendas for these meetings
Note: The items listed in 5.f may be provided on a weekly or daily basis after the
team arrives on site.
All requested documents should be provided electronically where possible. Regardless of
whether they are uploaded to an internet-based file library, please provide copies on CD or
DVD. One copy of the CD or DVD should be provided to the resident inspector at the site; and
one additional copy should be provided to the team lead, to arrive no later than January 18,
2019:
U.S. NRC Region IV
Attn: Harry Freeman
1600 E. Lamar
Arlington, TX 76011
PAPERWORK REDUCTION ACT STATEMENT
This request does not contain new or amended information collection requirements subject to the Paperwork
Reduction Act of 1995 (44 U.S.C. 3501 et seq.). Existing information collection requirements were approved by
the Office of Management and Budget, control number 3150-0011.
SUNSI Review: ADAMS:
Non-Publicly Available Non-Sensitive Keyword: NRC-002
By: HAF Yes No
Publicly Available
Sensitive
OFFICE
SRI:IPAT
RI:IPAT
PSI:PSB1
RI:PBC
ATL:IPAT
C:PBC
ATL:IPAT
NAME
HFreeman
PJayroe
CJewett
BParks
RKellar
JKozal
RKellar
SIGNATURE
/RA/
/RA/
/RA/
/RA/
/RA/
/RA/
/RA RVA for/
DATE
03/27/2019
03/27/2019
03/27/2019
04/01/2019
04/02/2019
04/04/2019
04/05/2019